Effect of metallurgical condition on irradiation-assisted stress corrosion cracking of commercial stainless steels

J. T. Busby, G. S. Was

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

4 Scopus citations

Abstract

Irradiation-assisted stress corrosion cracking (IASCC) is complex phenomenon that is sensitive to the metallurgical condition of the alloy. The objective of this study is to systematically examine the influence of the metallurgical condition on the radiation-induced changes and IASCC susceptibility in stainless steels. A 304 alloy (solution-annealed) and a 316 alloy from a PWR baffle-bolt in three conditions (cold-worked, solution-annealed and a desensitized state designed to form coherent grain-boundary carbides) were irradiated with 3.2-MeV protons at 360°C to 5.5 dpa. Constant extension rate tensile tests were performed in simulated BWR (NWC) and primary water (PW) environments. Both alloys were susceptible to IGSCC in the solution-annealed condition in both environments. The desensitized state was extremely susceptible in the oxygenated environment, due to residual sensitization. In the PW environment, cracks initiated but did not propagate, indicating a potentially beneficial influence of carbides. The cold-worked state was resistant to IG cracking in both PW and BWR-NWC environments.

Original languageEnglish
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages255-266
Number of pages12
StatePublished - 2005
Externally publishedYes
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: Aug 14 2005Aug 18 2005

Publication series

NameProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors

Conference

Conference12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Country/TerritoryUnited States
CitySalt Lake City, UT
Period08/14/0508/18/05

Keywords

  • Cold work
  • IASCC
  • Sensitization
  • Stainless steel

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